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Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: August 1960 Through November 1962
Report documenting experience gained by operating the spare PRTR Primary Process Pump. This includes descriptions of equipment used, testing procedures, and operating history.
Date:
March 1963
Creator:
Scott, P. A.
System:
The UNT Digital Library
Specifications for Vibrationally Compacted UO2 Nested Tubular Fuel Element (PRTR MARK II-C)
Report describing the vibrationally compacted UO2 nested tubular fuel element, its design specifications, fabrication, and assembly.
Date:
March 1963
Creator:
Milhollen, M. K.
System:
The UNT Digital Library
High Temperature Short-Time, Uranium Carbide-Metal Reactions
Report investigating the compatibility of uranium carbide with tungsten, tantalum, molybdenum, Zircaloy-2, AISI 304L SS, Inconel, Hastelloy F, niobium-1% Zr, and niobium-33% Ta-1% Zr. These pairs were heated together at 1000 C and above for ten minutes.
Date:
March 1963
Creator:
Christensen, J. A.
System:
The UNT Digital Library
Strength and Metallurgical Properties of the Zircaloy-2 Pressure Tubes for the Plutonium Recycle Test Reactor
Report describing the properties of the Zircaloy pressure tubes at the Plutonium Recycle Test Reactor. Topics include the fabrication of these tubes, their mechanical properties, and operating stresses.
Date:
March 1962
Creator:
Knecht, R. L. & Pankaskie, P. J.
System:
The UNT Digital Library
Fretting Corrosion in the Plutonium Recycle Test Reactor
Report that summarizes out-of-reactor tests undertaken to determine operating conditions, estimate damage from and extent of fretting corrosion, and describe continuing tests planned to monitor and eliminate this corrosion.
Date:
March 1964
Creator:
Winegardner, W. K.
System:
The UNT Digital Library
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H
Report describing the fabrication of of the I-H aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR), including the materials used and design specifications. Appendix begins on page 28.
Date:
March 1961
Creator:
Sharp, R. E.
System:
The UNT Digital Library
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 4, Gas-Cooled Loop Anaysis
Plutonium Recycle Test Reactor (PRTR) final safeguards analysis involving a gas-cooled loop.
Date:
March 1962
Creator:
Wittenbrock, N. G.
System:
The UNT Digital Library
Specifications for Swaged UO2 19-Rod Cluster, PRTR Fuel Element Mark 1
Specifications including detail dimension, materials, fabrication steps, acceptance criteria, and final assembly steps for the swaged uranium dioxide, 19-rod cluster Plutonium Recycle Test Reactor fuel element.
Date:
March 15, 1960
Creator:
Millhollen, M. K.
System:
The UNT Digital Library
Halogen Collector Test Program
Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date:
March 1, 1960
Creator:
Arthur D. Little, Inc.
System:
The UNT Digital Library
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G
Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).
Date:
March 1961
Creator:
Freshley, M. D.
System:
The UNT Digital Library
Factors Affecting Fluidization of Uranium Trioxide Powders
Study of factors, such as the average particle size and particle-size distribution, which affect the fluidization properties of uranium trioxide powders.
Date:
March 1, 1958
Creator:
Johnson, B. M.
System:
The UNT Digital Library
Magnetic Force Welding Sintered Aluminum Powder Materials
Report discussing the use of sintered aluminum powder for nuclear fuel cladding. This report includes descriptions of pertinent materials and experimental procedures.
Date:
March 1962
Creator:
Mills, L. E.
System:
The UNT Digital Library
Final Design Report: DR-1 Gas Loop
Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.
Date:
March 1961
Creator:
Baars, R. E.
System:
The UNT Digital Library
An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept
From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept."
Date:
March 1, 1958
Creator:
Hanford Works
System:
The UNT Digital Library
Corrosion resistance and magnetic susceptibility
From summary: "On the basis of the tests described herein, the corrosion characteristics of T-347 welded stainless steel are found not to be affected by the magnetic properties of the welds even though these properties are likely the result of the presence of the ferritic structure."
Date:
March 7, 1949
Creator:
Koenig, W. W. & Heckman, R. L.
System:
The UNT Digital Library
The Coulometric Determination of Acid
Introduction: "The need for a method of acid determination which could be used for small samples and easily adapted to remote control led to the investigation of the use of electrolytically generated base for the titration of acid in certain solutions. The use of electrolytically generated base for the titration of acetic acid in the presence of nitric acid has been reported (1)."
Date:
March 1, 1950
Creator:
Carson, W. N. & Ko, Roy
System:
The UNT Digital Library
The Development of Plutonium Electrodeposition Methods : Interim Report
From introduction: "The following report presents a body of information obtained in the Health Instrument Development Laboratory from September, 1948, to the present, and is intended to be a preliminary review of [the study of electrodeposition of plutonium]. Many improvements in technique and methods and investigations along lines not explored are suggested by the present work. These will be undertaken as time permits, and reported at a later time."
Date:
March 1, 1950
Creator:
Schwendiman, L. C.
System:
The UNT Digital Library
The Gasometric Determination of Nitrite and Sulfamate
This report covers an investigation made to develop a gasometric determination that can determine 1.2 x 10-(-5) g. of nitrite with a precision (99% limits) of +/- 8%, and discusses how this procedure works.
Date:
March 6, 1950
Creator:
Carson, W. N.
System:
The UNT Digital Library
Infrared Absorption Measurements Indicating Intermolecular Association of Water and Hexone
This report analyzes infrared absorption measurements that were made in the regions of carbonyl band and hydroxyl band absorptions on solutions of water in hexone and water in acetone, confirming intermolecular association of water and hexone.
Date:
March 8, 1950
Creator:
Moore, R. H.
System:
The UNT Digital Library
Corrosion of Stellite in MJ-1 Streams
The following report provides data from completed tests for corrosion testing of stellite-T347 stainless steel test cylinders.
Date:
March 8, 1950
Creator:
Koenig, W. W.
System:
The UNT Digital Library
The Determination of Tributyl Phosphate in Deodorized Shell Base with the Infrared Spectrometer
The following report describes methods used to determine tributylphosphate in a deodorized shell base. An infrared absorption method is developed to emphasize toward determination of TBP in RCW streams, the organic waste streams.
Date:
March 10, 1950
Creator:
Moore, R. H.
System:
The UNT Digital Library
Solubility relationships of acidified stored metal wastes
The reports aims to determine the solubility limitation of concentrations of uranium in the food preparation step of the tributyl phosphate waste metal recovery process, and the subsequent solubilities in the RA column.
Date:
March 24, 1950
Creator:
Curtis, M. H.
System:
The UNT Digital Library
Properties of the System: Uranyl Nitrate-Aluminum Nitrate - Nitric Acid (or Sodium Hydroxide) - Sodium Nitrate - Water - Hexone
This report discusses properties of the Redox process. Density, apparent molar volumes and viscosity are all described.
Date:
March 22, 1949
Creator:
Burger, L. L.; Rehn, I. M.; Schmidt, H. R. & Slansky, C. M.
System:
The UNT Digital Library
The Surface Preparation of Uranium for X-Ray Diffraction Studies by the Spectrometer Technique
A report which describes a number of experiments conducted to compare the effects of different methods of surface preparation on x-ray diffraction patterns of uranium obtained by the spectrometer technique.
Date:
March 24, 1949
Creator:
Bach, J. H. & Burnham, J. B.
System:
The UNT Digital Library